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Category:Letter
MONTHYEARIR 05000335/20250102024-10-21021 October 2024 Notification of St. Lucie Plant Units 1 & 2 Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000335/2025010 and 05000389/2025010 ML24227A9702024-10-18018 October 2024 Letter to Kenneth Mack Dir, License and Reg Compliance, NextEra Energy, Inc Response to Request Re Engagement Re Sub License Renewal Environmental Review - St Lucie Nuclear Plant 1 and 2 L-2024-085, Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results2024-10-15015 October 2024 Refueling Outage SL1-32 Low Pressure Turbine Rotor Inspection Results L-2024-165, Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made2024-10-14014 October 2024 Report of 10 CFR 50.59 Plant Changes, Tests and Experiments Made L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) ML24255A3092024-09-30030 September 2024 SLRA - Revised SE Letter L-2024-155, Subsequent License Renewal Application, Third Annual Update2024-09-27027 September 2024 Subsequent License Renewal Application, Third Annual Update L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes 05000335/LER-2024-001, Unplanned Reactor Scram2024-09-25025 September 2024 Unplanned Reactor Scram IR 05000335/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000335/2024011 and 05000389/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-138, License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles2024-09-11011 September 2024 License Amendment Request L-2024-138, Fuel Methodology Changes in Support of St. Lucie, Unit 2 Transition to 24-Month Fuel Cycles L-2024-148, Submittal of Offsite Dose Calculation Manual (Odcm), Revision 552024-09-0909 September 2024 Submittal of Offsite Dose Calculation Manual (Odcm), Revision 55 IR 05000335/20240052024-08-22022 August 2024 Updated Inspection Plan for St. Lucie, Units 1 & 2 - Report 05000335/2024005 and 05000389/2024005 L-2024-140, Cycle 28 Core Operating Limits Report2024-08-14014 August 2024 Cycle 28 Core Operating Limits Report L-2024-133, Snubber Program Plan Submittal2024-08-14014 August 2024 Snubber Program Plan Submittal L-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis IR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval 05000389/LER-2024-003, Unplanned Reactor Scram2024-08-0505 August 2024 Unplanned Reactor Scram ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan 05000389/LER-2024-002-01, Safety Injection Tank Vent Through Wall Leakage2024-07-11011 July 2024 Safety Injection Tank Vent Through Wall Leakage L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches L-2024-104, Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports IR 05000335/20244012024-06-0303 June 2024 Security Baseline Inspection Report 05000335/2024401 and 05000389/2024401 ML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation IR 05000335/20240012024-05-10010 May 2024 Integrated Inspection Report 05000335/2024001 and 05000389/2024001 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report ML24108A0632024-04-18018 April 2024 – Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report ML24093A2612024-04-0202 April 2024 – Investigation Summary, Office of Investigations Case Number 2-2023-005 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda 2024-09-09
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I REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC: STELLO V ORG: UHRIG R E DOCDATE: 02f21/78 NRC FL PWR 8c LIGHT DATE RCVD: 02f 24f 78 DOCTYPE: LETTER NOTARIZED: YES COPIES RECEIVED
SUBJECT:
LTR 3 ENCL 0 RESPONSE TO NRC"S LTR DTD Oif30f78... FURNISHING INFO ON APPLICANT"S UNIT 1 STEAM GENERATORS.
PLANT NAME: ST LUCIE Ni REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:
DISTRIBUTION OF THIS MATERIAL IS. AS FOLLOWS +++++>>++>>>>+>>>>
RESPONSES TO STEAM GENERATOR CODE A023)
QUESTIONNARE'DISTRIBUTION FOR ACTION: BRANCH ( ~
LY<7)'G INTERNAL: FILE~~4~I TR Ol L NRC PDR++LTR ONLY(i)
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SHAO+4~LTR ONLY ( 1 ) BAER++LTR ONLY(l)
BUTI ER+4LTR ONLY<i) GRIMES~+LTR ONLY< 1)
J COLLINS~~LTR ONLY(1>
EXTERNAL: LPDR'S FT PIERCE FL4~+LTR ONLY< 1)
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NSIC4<4LTR ONI Y(1)
RON GAMBLE+4ILTR ONLY(6)
KEN HERR ING+4LTR ONLY < 6)
ACRS CAT B++LTR ONLY(16)
DISTRIBUTION: LTR 50 ENCL 0 CONTROL NBR: 780580015 SIZE: 3P
%%%%%%%%%%%%%%%4%%0E%% 4%% 4 4.%%%% 4 %% 4 % THE END
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FLORIDA POWER & LIGHT COMPANY February 21, 1978 L-78-61 Office of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating, Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Stello:
Re: St. Lucie Unit 1 Docket No. 50-335 .. XYi COhLA(ISS lON STEAM GENERATOR INFORMATION bi@ %atlatl The following information on the St. Lucie Unit ~s cap generators is provided in response to your letter of>
January 30, 1978:
St. Lucie Unit 1 is scheduled for its first refueling outage around the first of April, 1978. A steam generator inspection has been planned for this outage and will include some in-spection of the tube support plates for possible cracking.
The inspection program was developed in consultation with Combustion Engineering and is based on the findings at Millstone Unit 2. This inspection will determine if any problems now exist with the steam generator upper horizontal drilled tube support plates.
After reviewing St. Lucie's history we find that chloride intrusion has been very limited and chloride exposure has been significantly less than that reported for Millstone Unit
- 2. It has been shown in the laboratory that chlorides are definitely implicated in the denting process and it is believed that'ood chemistry will minimize denting. This is supported by recent steam generator inspections at Ft. Calhoun and Calvert Cliffs where there is good chemistry and the absence of denting. Therefore, we believe that St.'ucie Unit 1 is free of denting, or at worst, that the denting phenomenon may be in an incipient stage. Thus, it is concluded that signifi-cant support plate cracking does not exist because such crack-.
ing results from stresses created only when extensive denting is present.
Florida Power 6 Light Company has concluded that operation of St. Lucie Unit 1 will not create undue risk to the health and safety of the public. This conclusion resulted from the re-view and consideration of the following information.
7gO5800 i5 PEOPLE... SERVING PEOPLE
(1) St. Lucie is a relatively new plant which has operated with good secondary water chemistry (i. e., very limited chloride ingress) . This supports our contention that denting is not present, or in the unlikely event that started, that it it has has not progressed signifi-cantly.
(2) The unit will only operate a short while before it(Inspection will undergo a steam generator inspection tentatively planned for April, 1978).
(3) St. Lucie's total operating interval is consi-dered to be conservatively bounded by the Millstone Unit 2 experience (i.e., Millstone has operated longer than St. Lucie and has had greater chloride intrusion).
(4) Industry research and field experience have demonstrated that extensive denting and support plate cracking eventually produce steam generator tube leaking. Furthermore, these leaks (in inconel tubes) develop and propagate very slowly, thus enabling safe and orderly shutdown of the units.
(5) St. Lucie has not had. any steam generator tube leaks.
In summary, we are keeping up to date with steam generator related activities within the industry, so we are familiar with the types of corrective action which could be imple-mented if the need arises. In the unlikely event, that. ab-normal findings result from the planned steam generator inspections, they will be evaluated jointly with the vendor to develop appropriate corrective action.
Very truly yours, Robert E. Uhrig Vice President, REU/MAS/RSA/bab cc: Mr. Games P. O'Reilly, Region II Harold F. Reis, Esquire Mr. Pete B. Erickson
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Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that, the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uhrig Subscribed and sworn to before me this
~J~ day of 19 )Z NOTARY PUBLIC, in and for the County of Dade, State of Florida NOTARY FUCuC STAN OF fLORfDA et LRRQC MY CC).t'8ISGIOl4 f>;f'IRc3 AUGUST 24, 19C>
Ny commission expires: <o~c~ iURU teYt'~o.nwcc4a kiln
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